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The Riddle Of Nde For Embrittlemient Detection

Published online by Cambridge University Press:  10 February 2011

M. Blaszkiewicz
M. Blaszkiewicz*
Affiliation:
Advanced Materials Department, Westinghouse Science & Technology Center, Pittsburgh, PA 15235
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Abstract

The ability to nondestructively determine the level of irradiation induced degradation in nuclear reactor pressure vessels (RPVs) would enhance the integrity assessment currently used by the nuclear industry. Presently, destructive testing of Charpy specimens from surveillance capsules is used to approximate the RPV upper shelf energy and the ductile-to-brittle transition temperature, and approved models and guidelines are used to determine the state of embrittlement. However, these models and surveillance programs do not always provide enough accurate information to support decisions for premature RPV life termination, life continuation to license expiration, or life renewal and extension by means of annealing. Effective nondestructive techniques would extend the usefulness of the surveillance material by reducing the amount of material used for destructive studies, and ultimately by allowing tests to be performed directly on the RPV. Nondestructive techniques, ranging from electrical resistivity to hyperfine interactions, have been, and continue to be, explored for use in embrittlement assessment. The current states of these various techniques are discussed, and future directions for research are suggested.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 503: Symposium JJ – Nondestructive Characterization of Materials in Aging Systems , 1997 , 169
Copyright
Copyright © Materials Research Society 1998

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References

REFERENCES

1. The American Heritage Dictionary, 3rd Edition, Dell Publishing, New York, 1994.Google Scholar
2. Pavinich, W. A., Griesbach, T. J., and Server, W. L., “An Overview of Radiation Embrittlement Modeling for Reactor Vessel Steels,” in Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Fourth Volume). pp. 99–117, ASTM STP 1170, Edited by Steele, L. E., ASTM, Philadelphia, PA, 1993.Google Scholar
3. Odette, G. R. and Lucas, G. E., “Irradiation Embrittlement of Reactor Pressure Vessel Steels: Mechanisms, Models, and Data Correlations,” in Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Second Volume), pp. 206–241, ASTM STP 909, Edited by Steele, L. E., ASTM, Philadelphia, PA, 1986.Google Scholar
4. Williams, T. J., Burch, P. R., English, C. A., and de la cour Ray, P. H. N., “The Effect of Irradiation Dose Rate and Temperature, and Copper and Nickel Content, on the Irradiation Shift of Low Alloy Steel Submerged Arc Welds,” in Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors pp. 121, Edited by Theus, G. J. and Weeks, J. R., TMS, 1988.Google Scholar
5. Burke, M. G., and Mager, T. R., “Neutron Radiation Embrittlement and Microstructural Characterization of Ferritic Steels,” EPRI Report TR- 103173, 1995.Google Scholar
6. Waeber, W. B., Solt, G., Tipping, P., Frisius, F., and Mercier, O. M., “Correlation Between Measured and Microphysical Parameters for an Irradiated Pressure Vessel Material,” Proceedings of the Tenth Conference on Structural Mechanics in Reactor Technology, pp. 149–154, 1989.Google Scholar
7. Liaw, P. K., Leax, T. R., Drinon, D. S., and Rishel, R. D., “Nondestructive Evaluation of Irradiated Pressure Vessel Steels from Surveillance Capsules,” Westinghouse Science and Technology Center Internal Report, 1993.Google Scholar
8. Stubbins, J. F., Williams, J. G., Ougouag, A. M., Patel, J. U., and Shong, W. -J., “Measurement of Irradiation Damage in Nuclear Pressure Vessel Steels by Magnetic Prqperties Change,” in Proceedings of the Fifth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. Edited by Simonen, E. P., American Nuclear Society, 1992.Google Scholar
9. Shong, W. -J, Williams, J. G., and Stubbins, J. F., “Interrogation of Radiation Effects in Nuclear Pressure Vessel Steels Using Magnetic Properties Measurements,” ANS Transactions, pp. 192–193, November 1993.Google Scholar
10. Stubbins, J. F., Shong, W. -J., Giacobbe, M., Ougouag, A. M., and Williams, J. G., “Pressure Vessel Steel Embrittlement Monitoring by Magnetic Properties Measurements,” in Small Specimen Test Techniques Applied to Nuclear Reactor Vessel Thermal Annealing and Plant Life Extension, pp. 5–15, ASTM STP 1204, Edited by Corwin, W. R., Haggag, F. M., and Server, W. L., American Society for Testing and Materials, Philadelphia, PA, 1993.Google Scholar
11. Devine, M. K., Jiles, D. C., Liaw, P. K., Rishel, R. D., and Drinon, D. S., “Magnetic Property Changes in Various Structural Steels Due to Irradiation,” in Progress in Quantitative Nondestructive Evaluation, Edited by Thompson, D. O. and Chimenti, D. E., Plenum Press, 1993.Google Scholar
12. Bergner, F., Kohler, B., and Popp, K., “The Role of Microstructure in the Propagation of Ultrasound in Bainitic Low-Alloy Steels,” Int. J. Pres. Ves. and Piping, 55, pp. 251–260, 1993.Google Scholar
13. Yoneyama, H, Ooka, N., Futamura, Y., Hirano, T., Yoshida, K., and Kobayashi, H., “Study of Characterizing Irradiation Embrittlement of Pressure Vessel Steel by Ultrasonic Technique,” in Nuclear Plant Systems/Components Aging Management and Life Extension pp. 57–61, ASME PVP-228, Edited by Kisisel, I. T., Sinnapan, J., Carlson, R. W., and Lake, W. H., 1992.Google Scholar
14. Van Duysen, J. C., Bourgoin, J., Moser, P., and Janot, C., “Study by Positron Annihilation of Neutron Damage in a Pressurized Water Reactor (PWR) Pressure Vessel Steel After a 13-Year Irradiation in the CHOOZ A Reactor Surveillance Program,” in Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Fourth Volume). pp. 132–138, ASTM STP 1170, Edited by Steele, L. E., ASTM, Philadelphia, PA, 1993.Google Scholar
15. Cumblidge, S. E., Motta, A. T., and Catchen, G. L., Personal Communication, 1996.Google Scholar
16. Munier, A., Schaller, R., Mercier, O., and Waeber, W. B., “Interactions of Defects with Dislocations in Reactor Pressure Vessel Steels,” in Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Fourth Volume). pp. 269–282, ASTM STP 1170, Edited by Steele, L. E., ASTM, Philadelphia, PA, 1993.Google Scholar
17. Van Ouytsel, K., Personal Communication, 1995.Google Scholar
18. Chihoski, R. A., “Solving for Thermal History and Metallurgical Condition of a Quenched and Aged Aluminum Alloy through Conductivity and Hardness Properties,” in Nondestructive Methods from Material Property Determination, Edited by Ruud, C. O. and Green, R. E. Jr., Plenum Press, 1984.Google Scholar